Thermomechanische Modellierung eines Reaktordruckbehälters in der Spätphase eines Kernschmelzunfalls

Considering the late in-vessel phase of an unlikely core melt down scenario in a light water reactor (LWR) with the formation of a corium pool in the lower head of the re-actor pressure vessel (RPV) the possible failure modes of the RPV and the time to failure have to be investigated to assess the p...

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Bibliographic Details
Main Author: Willschütz, H.-G.
Other Authors: Forschungszentrum Rossendorf, Institut für Sicherheitsforschung
Format: Others
Language:deu
Published: Forschungszentrum Dresden 2010
Subjects:
Online Access:http://nbn-resolving.de/urn:nbn:de:bsz:d120-qucosa-28520
http://nbn-resolving.de/urn:nbn:de:bsz:d120-qucosa-28520
http://www.qucosa.de/fileadmin/data/qucosa/documents/2852/8141.pdf